Tritium permeation measurements with and without the presence of liquid lithium flouride-beryllium fluoride salt, and test of tritium barrier coating for the High Tmeperature Fluoride Salt Reactor. Also demonstrated the use of a "graphite vertical" position outside the core for high temperature neutron irradiations.

Irradiation of a large set of candidate high performance LWR clad materials for post-irradiation property testing

Fluoride Salt 3 (FS-3)**

Inert gas, 700 °C

2016

Tritium transport measurements on SiC/SiC and graphite samples irradiated in liquid lithium fluoride-beryllium fluoride salt for the High Temperature Fluoride Salt Reactor. Samples from U.S. DOE program and Chinese Academy of Sciences